| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Analysis of Benefits and Risks of Thorium and 233U Introduction in the VVER-1200 Fuel Cycle in the Fusion-Fission Reactor System
|
Gurin, A. V.
|
|
|
86 |
8 |
p. 1874-1881
|
artikel
|
| 2 |
Analysis of Readings of Background Cores of In-Reactor Detectors
|
Musihin, A. M.
|
|
|
86 |
8 |
p. 1778-1781
|
artikel
|
| 3 |
Beyond Design Basis Accident with Blackout of the RBMK. Analysis of the Possibility of Recriticality Occurrence
|
Krayushkin, A. V.
|
|
|
86 |
8 |
p. 1907-1913
|
artikel
|
| 4 |
Calculation of the Neutronic Characteristics of a HTGR for the Verification of the MCU-HTR Software Package
|
Grol, A. V.
|
|
|
86 |
8 |
p. 1827-1837
|
artikel
|
| 5 |
Comparison of the Effect of Nuclear Data Uncertainty on the Accuracy of Prediction of the Isotope Composition for UO2 and MOX Fuel in Burnup Calculations for a PWR Cell
|
Pisarev, A. N.
|
|
|
86 |
8 |
p. 1804-1811
|
artikel
|
| 6 |
Computational Analysis of the Possible Location of Ionization Chambers in Fast Reactors
|
Zizin, M. N.
|
|
|
86 |
8 |
p. 1838-1848
|
artikel
|
| 7 |
Consideration of the Evolution of Limited Chains of Nuclear Fission in the Study of Probabilistic Neutron Processes in a Neutron Multiplication System
|
Lutsenko, A. V.
|
|
|
86 |
8 |
p. 1757-1762
|
artikel
|
| 8 |
Determination of Energy Release from Gamma Radiation in Experimental Channels of the IR-8 Reactor
|
Trofimchuk, V. V.
|
|
|
86 |
8 |
p. 1768-1777
|
artikel
|
| 9 |
Development of Empirical Correlations for Assessment of the Value of the Conversion Coefficient of Postulated Steam Explosion under Severe Accident at VVER Reactor Plant
|
Nikolaeva, A. V.
|
|
|
86 |
8 |
p. 1935-1942
|
artikel
|
| 10 |
Estimation of the Effective Multiplication Factor and the Prompt Neutron Multiplication Constant for Fast Neutron Systems
|
Ershova, L. S.
|
|
|
86 |
8 |
p. 1763-1767
|
artikel
|
| 11 |
Evaluation of the Possibility of Using the Full Load of MOX Fuel in the VVER-600 Reactor
|
Trapeznikov, I. N.
|
|
|
86 |
8 |
p. 1856-1862
|
artikel
|
| 12 |
Facility for Testing MSR Materials at the NRC Kurchatov Institute
|
Abalin, S. S.
|
|
|
86 |
8 |
p. 1914-1920
|
artikel
|
| 13 |
Fuel Cycle of the LiF–BeF2 Molten Salt Actinide Burner Reactor
|
Zakirov, R. Ya.
|
|
|
86 |
8 |
p. 1894-1901
|
artikel
|
| 14 |
Grain Refinement of the HAZ Metal due to Welding
|
Chernobaeva, A. A.
|
|
|
86 |
8 |
p. 1921-1927
|
artikel
|
| 15 |
KIR2 Software Complex for Simulation of a Stationary and Nonstationary Particle Transport by the Monte Carlo Method
|
Belousov, V. I.
|
|
|
86 |
8 |
p. 1812-1817
|
artikel
|
| 16 |
Modeling the Behavior of Tritium in a Molten Salt Nuclear Reactor
|
Gatsa, P. V.
|
|
|
86 |
8 |
p. 1953-1963
|
artikel
|
| 17 |
On Conditions of Development of Neutronic Mechanisms of Instability on a Portion of Groups of Emitters of Delayed Neutrons
|
Kresov, D. G.
|
|
|
86 |
8 |
p. 1782-1784
|
artikel
|
| 18 |
On Radiocarbon in Uranium Graphite Reactors
|
Davydova, G. B.
|
|
|
86 |
8 |
p. 1902-1906
|
artikel
|
| 19 |
Optimal Stabilization of Reactor Power with Preliminary Identification of Its Characteristics under Conditions of Uncontrolled External Influences
|
Degtyarev, A. M.
|
|
|
86 |
8 |
p. 1785-1794
|
artikel
|
| 20 |
Peculiarities of Changes in the Isotopic Composition of Pilot Fuel Elements of a VVER-SKD Reactor under Successive Irradiation in a Fast and Thermal Neutron Spectrum
|
Blandinsky, V. Yu.
|
|
|
86 |
8 |
p. 1849-1855
|
artikel
|
| 21 |
Radiolysis of the Coolant during the Decomposition of a Hydrogen Solution near the Saturation Temperature in VVER Reactors
|
Ivanov, A. S.
|
|
|
86 |
8 |
p. 1943-1952
|
artikel
|
| 22 |
Raw Material Effect on the Characteristics of the Fission and Fusion Reactor System
|
Andrianova, E. A.
|
|
|
86 |
8 |
p. 1882-1886
|
artikel
|
| 23 |
RC Code for Calculating Doses from Radioactive Releases to the Atmosphere
|
Geraskin, I. N.
|
|
|
86 |
8 |
p. 1818-1826
|
artikel
|
| 24 |
Study on Minor Actinide Incineration in Molten Salt Reactors with Uranium or Plutonium Loadings
|
Kotov, Ya. A.
|
|
|
86 |
8 |
p. 1887-1893
|
artikel
|
| 25 |
Transmission of Neutrons by a Single Crystal of Bismuth Germanate
|
Parshin, P. P.
|
|
|
86 |
8 |
p. 1749-1756
|
artikel
|
| 26 |
Use of Eutectic Na–Tl Coolant in a Modular Fast Reactor
|
Alekseev, P. N.
|
|
|
86 |
8 |
p. 1928-1934
|
artikel
|
| 27 |
Validation of ENDF/B-7.1 Library for PIK-04 Critical Experiments
|
Onegin, M. S.
|
|
|
86 |
8 |
p. 1795-1803
|
artikel
|
| 28 |
Validation of the KORSAR/GP Code Based on the Results of Tests of Maneuvering Conditions of a VVER Reactor with an Extended Control Range
|
Nikolaev, A. L.
|
|
|
86 |
8 |
p. 1863-1873
|
artikel
|
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